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Abstract

The effects of plasma disruption events on the structural integrity of the Tokamak inboard and outboard first wall foreseen for NET (Next European Torus) are investigated. The choice and position of the fastening and guiding support system combined with the strengthening of the back plate and of the vertical extensions can have a major impact on their integrity. The transient nature of the electromagnetic-type phenomena and the complex multilayer structure of the internal components, including different conducting materials, requires a fully three-dimensional dynamic analysis, based on a thin shell formulation, for both the electrical and mechanical computations. The present paper considers detailed mechanical design aspects of the inboard and outboard first wall segments, such as the choice for the support system position combined with additional stiffening of the rear part. The proper solution through the comparative study of various options is described.

Additional information

Authors: CRUTZEN Y R, JRC ISPRA ESTAB. (ITALY);FARFALETTI CASALI F JRC ISPRA ESTAB. (ITALY), JRC ISPRA ESTAB. (ITALY)
Bibliographic Reference: SMIRT-10 (STRUCTURAL MECHANICAL IN REACTOR TECHNOLOGY), ANAHEIM, CA. (USA), AUG. 14-22, 1989, AVAILABILITY: CEC-LUXEMBOURG, DG-XIII-C-3, POB 1907, MENTIONING PAPER EN 34205 ORA
Availability: Can be ordered online
Record Number: 1989126105100 / Last updated on: 1989-06-01
Category: PUBLICATION
Available languages: en